HT-7U TF and PF conductor design

• Published in: Cryogenics (Guildford) Vol. 40; no. 8; pp. 531 - 538
• Main Authors: Weng, P.D, Bi, Y.F, Chen, Z.M, Li, B.Z, Fang, J
• Format: Journal Article Conference Proceeding
• Language: English
• Published: Oxford Elsevier Ltd 2000; Elsevier
• Subjects: AC losses; Applied sciences; Controled nuclear fusion plants; Copper; Electric losses; Energy; Energy. Thermal use of fuels; Exact sciences and technology; Installations for energy generation and conversion: thermal and electrical energy; Niobium alloys; Stability; Superconducting cables; Superconducting materials; Superconductors; Surface treatment; Asia; China; AC losses; Superconductors; Stability; Tokamak; Nuclear fusion reactor; Cable in conduit; Poloidal field; Cryogenics; Superconducting cable; Nuclear reactor
• ISSN: 0011-2275; 1879-2235
• DOI: 10.1016/S0011-2275(01)00009-1

The HT-7U tokamak is a Chinese National Project. The mission of the project is to build an advanced full superconducting tokamak. NbTi strands are selected as the superconducting material. The copper ratio of the strands is 3.5 times less than that required by optimization; therefore, increasing the copper fraction in the cable is a key issue for conductor stability. Several versions of CICC with different configurations and surface treatment have been investigated and experimented with. Using segregated copper is a cost-saving option available to the HT-7U project.